IR 05000338/2025003
| ML25337A351 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 12/05/2025 |
| From: | Shawn Smith Division of Operating Reactors |
| To: | Carr E Dominion Energy |
| References | |
| IR 2025003, IR 2024001 | |
| Download: ML25337A351 (0) | |
Text
SUBJECT:
NORTH ANNA POWER STATION, UNITS 1 AND 2 - INTEGRATED INSPECTION REPORT 05000338/2025003 AND 05000339/2025003; AND INSPECTION REPORT 07200056/2024001
Dear Eric S. Carr:
On September 30, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at North Anna Power Station, Units 1 and 2. On November 19, 2025, the NRC inspectors discussed the results of this inspection with Mr. James Jenkins, site vice president, and other members of your staff. The results of this inspection are documented in the enclosed report.
Due to the temporary cessation of government operations, which commenced on October 1, 2025, the NRC began operating under its Office of Management and Budget-approved plan for operations during a lapse in appropriations. Consistent with that plan, the NRC operated at reduced staffing levels throughout the duration of the shutdown. However, the NRC continued to perform critical health and safety functions and make progress on other high-priority activities associated with the ADVANCE Act and Executive Order 14300. On November 13, 2025, following the passage of a continuing resolution, the NRC resumed normal operations.
However, due to the 43-day lapse in normal operations, the Office of Nuclear Reactor Regulation granted the Regional Offices an extension on the issuance of the calendar year 2025 inspection reports that should have been issued by November 13, 2025, to December 31, 2025. The NRC resumed the routine cycle of issuing inspection reports on November 13, 2025.
No findings or violations of more than minor significance were identified during this inspection.
December 5, 2025 This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, Steven P. Smith, Chief Projects Branch 6 Division of Operating Reactor Safety Docket Nos. 05000338 and 05000339; 07200056 License Nos. NPF-4 and NPF-7
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000338 and 05000339; 07200056
License Numbers:
Report Numbers:
05000338/202500 and 05000339/2025003; 07200056/2024001
Enterprise Identifier:
I-2025-003-0029; I-2024-001-0046
Licensee:
Dominion Energy
Facility:
North Anna Power Station, Units 1 and 2
Location:
Mineral, Virginia
Inspection Dates:
July 1, 2025, to September 30, 2025
Inspectors:
K. Carrington, Senior Resident Inspector
P. Cooper, Senior Reactor Inspector
J. Diaz-Velez, Branch Chief
C. Even, Senior Project Engineer
K. Lei, Emergency Preparedness Inspector
D. Neal, Health Physicist
D. Orr, Senior Project Engineer
M. Rich, Emergency Preparedness Inspector
S. Roche Rivera, General Engineer Nran
A. Ruh, Senior Resident Inspector
D. Strickland, Senior Reactor Inspector
D. Turpin, Resident Inspector
J. Walker, Sr Emergency Preparedness Inspector
Approved By:
Steven P. Smith, Chief
Projects Branch 6
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at North Anna Power Station, Units 1 and 2, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.
List of Findings and Violations
No findings or violations of more than minor significance were identified.
Additional Tracking Items
None.
PLANT STATUS
Unit 1 began the inspection period operating at or near 100 percent rated thermal power (RTP). On September 7, 2025, the unit was shut down for refuel outage 1R31. The unit remained shut down through the end of the inspection period.
Unit 2 operated at or near 100 percent RTP for the entire inspection period.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors performed activities described in IMC 2515, Appendix D, Plant Status, observed risk significant activities, and completed on-site portions of IPs. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
REACTOR SAFETY
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 1, 'J' emergency diesel generator (EDG) walkdown following automatic start due to loss of 1J 4160 Bus voltage, on July 2, 2025
- (2) Unit 1, 'A' and 'B' quench spray system prior to testing on July 8, 2025
- (3) Unit 1, residual heat removal system walkdown during decreased reactor coolant system inventory, on September 10, 2025
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (1 Sample)
The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:
- (1) Fire Area 8, Unit 2, mechanical equipment room, on August 1, 2025 71111.08P - Inservice Inspection Activities (PWR)
The inspectors evaluated the reactor coolant system boundary, steam generator tubes, reactor vessel internals, risk-significant piping system boundaries, and containment boundary to determine if they were appropriately monitored for degradation and that repairs and replacements were appropriately fabricated, examined and accepted by reviewing the following activities in Unit 1 during refueling outage N1R31 from September 15 to September 25, 2025.
PWR Inservice Inspection Activities Sample - Nondestructive Examination and Welding
Activities (IP Section 03.01) (1 Sample)
The inspectors evaluated the following nondestructive examination and welding activities to verify if they were performed appropriately:
- (1) Ultrasonic Examination
- 4-RC-15/ SW-17, pipe-to-elbow, ASME class 1
- 6-SI-132/ SW-54, pipe-to-pipe, ASME class 1 Dye Penetrant Examination
- 4-RC-15/ SW-17, pipe-to-elbow, ASME class 1
- 14-RC-10/ 37, nozzle-to-pipe, ASME class 1 Visual Examination
- 1-RC-P-1B/ N01-N24, RCP main flange nuts, ASME class 1 Welding Activities
- Gas tungsten and shielded metal arc welding o
Service water pipe, 36.00-WS-2-151-Q3, ASME class 3 pipe, base metal repair (WO# 59203468181)
PWR Inservice Inspection Activities Sample - Vessel Upper Head Penetration Inspection
Activities (IP Section 03.02) (1 Sample)
The inspectors evaluated whether the licensee conducted the following vessel upper head penetration inspections and addressed any identified defects appropriately:
- (1) CRDM upper head penetrations 02, 07, 24, 57 PWR Inservice Inspection Activities Sample - Boric Acid Corrosion Control Inspection Activities (IP Section 03.03) (1 Sample)
The inspectors evaluated whether the licensee was managing the boric acid corrosion control program through a review of the following evaluations:
(1)
(2)
- (3) Boric acid walkdown - September 17, 2025 Reviewed engineering evaluations in WO# 59203397821 and 59203448308 Reviewed CR's 1300630, 1300729, 1300787, 1301197 (from NRC walkdown)
PWR Inservice Inspection Activities Sample - Steam Generator Tube Inspection Activities (Section 03.04) (1 Sample)
The inspectors evaluated whether the licensee was monitoring the steam generator tube integrity appropriately through a review of the following examinations:
- (1) Eddy Current Examinations
- Steam Generator A - Row 2 Column 25
- Steam Generator B - Row 36 Column 23
- Steam Generator C - Row 3 Column 79 Secondary Side Visual Examinations
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)
- (1) The inspectors observed and evaluated licensed operator performance in the control room during Unit 1 refueling outage (RFO) shutdown, on September 5, 2025.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated just-in-time training for the Unit 1 RFO shutdown, on September 4, 2025.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (2 Samples)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
- (1) CRs 1281217, 1280820, 1280046, 1261356, 1248515, and 1280276, associated with
'A' vent stack radiation monitor failures, on August 7, 2025
- (2) CR1286562, waste gas decay tank oxygen analyzer spiking, on August 12, 2025
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (2 Samples)
The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:
- (1) Unit 1 shutdown risk during service water header maintenance, turbine driven auxiliary feed water steam supply valve failure, and the Gordonsville offsite power line out of service, the week of September 1, 2025
- (2) Unit 1 shutdown risk for 'B' reactor coolant pump changeout and feedwater heater lifts with reactor water level at decreased inventory, the week of September 11, 2025
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (7 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) CR1292203, rod position indicator direct current power supplies out of service, on July 1, 2025
- (2) CR1296555, 2-HV-E-4C tripped, on July 17, 2025
- (3) CR1297537, fire door swap out from health physics to mechanical equipment room, on August 5, 2025
- (4) CR1294469, 2-PT-77.11C completed unsat, on August 12, 2025
- (5) CR1299276, through wall leak on 'B' service water header, on August 29, 2025
- (6) CR1286863, turbine driven auxiliary feedwater pump main steam trip valve limits exceeded, on September 10, 2025
- (7) CR1290602, 00-AAC-BC-1 unable to supply 40 amps at 125 VDC for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, on September 12, 2025
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1 Sample)
The inspectors evaluated the following temporary or permanent modifications:
- (1) Design change NA-25-00025, Alternate AC Diesel Temporary Battery Charger, on August 14, 2025
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Partial)
(1)
(Partial)
The inspectors evaluated refueling outage 1R31 activities (IP 71111.20, Sections a, b, and c1-3, c9-11, from September 1 to September 30, 2025.
71111.24 - Testing and Maintenance of Equipment Important to Risk
The inspectors evaluated the following testing and maintenance activities to verify system operability and/or functionality:
Post-Maintenance Testing (PMT) (IP Section 03.01) (7 Samples)
- (1) Unit 2, 'C' main control room chiller PMT following repair under WO59203466115, on July 28, 2025
- (2) Unit 2, 'A' main control room chiller PMT following cylinder repair under WO59203447289, on August 7, 2025
- (3) Unit 1, 'H' emergency diesel generator PMT, following 3-year maintenance under WOs 59203392254, 59203467248, 59203391823, 59203391827, 59203391829, 59203392251, 5920392256, 59203449779, and 59203424213, on August 9, 2025
- (4) Unit 2, auxiliary service water pump to service water header number 2 isolation valve PMT following actuator replacement under WO59203452579, on August 19, 2025 (5)
'B' service water header PMT following pipe leak repair under WO59203468181, on August 30, 2025 (6)
'B' boric acid transfer pump PMT following maintenance under WO59203423352, on September 2, 2025
- (7) Unit 1, 'J' emergency diesel generator PMT following automatic voltage regulator and governor interlock droop relay replacements under WOs 59203354204 and
59102713825, on September 24, 2025 Surveillance Testing (IP Section 03.01) (1 Sample)
(1)1-PT-57.1A, Emergency Core Cooling Subsystem - Low Head Safety Injection Pump (1-SI-P-A), on August 4, 2025
71114.02 - Alert and Notification System Testing
Inspection Review (IP Section 02.01-02.04) (1 Sample)
- (1) The inspectors evaluated the maintenance and testing of the alert and notification system during the week of September 15, 2025.
71114.03 - Emergency Response Organization Staffing and Augmentation System
Inspection Review (IP Section 02.01-02.02) (1 Sample)
- (1) The inspectors evaluated the readiness of the Emergency Response Organization during the week of September 15, 2025.
71114.04 - Emergency Action Level and Emergency Plan Changes
Inspection Review (IP Section 02.01-02.03) (1 Sample)
- (1) The inspectors evaluated submitted Emergency Action Level, Emergency Plan, and Emergency Plan Implementing Procedure changes during the week of December 15, 2025. This evaluation does not constitute NRC approval.
71114.05 - Maintenance of Emergency Preparedness
Inspection Review (IP Section 02.01 - 02.11) (1 Sample)
- (1) The inspectors evaluated the maintenance of the emergency preparedness program during the week of December 15, 2025.
71114.06 - Drill Evaluation
Additional Drill and/or Training Evolution (1 Sample)
The inspectors evaluated:
- (1) The inspectors observed licensee performance of a simulated DEP scenario, SXG-83, for emergency action level classifications, on July 29, 2025.
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls
Radiological Hazard Assessment (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated how the licensee identifies the magnitude and extent of radiation levels, identifies the concentrations and quantities of radioactive materials, and assesses radiological hazards.
Instructions to Workers (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated how the licensee instructs workers on plant-related radiological hazards and the radiation protection requirements intended to protect workers from those hazards.
Contamination and Radioactive Material Control (IP Section 03.03) (2 Samples)
The inspectors observed/evaluated the following licensee processes for monitoring and controlling contamination and radioactive material:
- (1) Workers exiting the radiologically controlled area (RCA) during a refueling outage.
- (2) Workers exiting Unit 1 containment during a refueling outage.
Radiological Hazards Control and Work Coverage (IP Section 03.04) (3 Samples)
The inspectors evaluated the licensee's control of radiological hazards for the following radiological work:
- (1) Unit 1 reactor coolant pump move
- (2) Unit 1 reactor coolant pump cavity foreign material retrieval
- (3) Unit 1 fuel movement activities
High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (5 Samples)
The inspectors evaluated licensee controls of the following high radiation areas (HRAs) and very high radiation areas (VHRAs):
- (1) Unit 2 volume control tank, gate 31 (LHRA)
- (2) Unit 2 demin alley, gate 57E (LHRA)
- (3) Unit 1 keyway (VHRA)
- (4) Unit 1 fuel movement barriers (LHRA)
- (5) Unit 1 reactor head shield doors (LHRA)
Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 03.06) (1 Sample)
- (1) The inspectors evaluated radiation worker and radiation protection technician performance as it pertains to radiation protection requirements.
71124.08 - Radioactive Solid Waste Processing & Radioactive Material Handling, Storage, &
Transportation
Radioactive Material Storage (IP Section 03.01) (1 Sample)
The inspectors evaluated the licensees performance in controlling, labeling and securing the following radioactive materials:
- (1) Auxiliary Building.
Radioactive Waste System Walkdown (IP Section 03.02) (1 Sample)
The inspectors walked down the following accessible portions of the solid radioactive waste systems and evaluated system configuration and functionality:
- (1) The liquid waste treatment tank and spent resin hold-up tank located in the decontamination building basement at elevation 251'.
Waste Characterization and Classification (IP Section 03.03) (2 Samples)
The inspectors evaluated the following characterization and classification of radioactive waste:
(1)10 CFR Part 61, Waste characterization for Dry Active Waste (DAW), Sample L109847-2, Common DAW, 05/05/2025.
(2)10 CFR Part 61, Waste characterization for Spent Resin Hold Up Tank, Sample L108913, 02/05/2025.
Shipping Records (IP Section 03.05) (3 Samples)
The inspectors evaluated the following non-excepted radioactive material shipments through a record review:
- (1) Shipment 23-BCO-07, Dry Active Waste, Low Specific Activity-I (LSA-I).
- (2) Shipment 24-BCO-07, High Integrity Container Resin (LSA-II).
- (3) Shipment 25-BCO-03, Dry Active Waste (LSA-II).
OTHER ACTIVITIES - BASELINE
71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04) (2 Samples)
- (1) Unit 1: SSFF (July 1, 2024, to June 30, 2025)
- (2) Unit 2: SSFF (July 1, 2024, to June 30, 2025)
MS08: Heat Removal Systems (IP Section 02.07) (3 Samples)
- (1) Unit 1: Heat Removal (auxiliary feedwater) (July 1, 2024, to June 30, 2025)
- (2) Unit 2: Heat Removal (auxiliary feedwater) (July 1, 2024, to June 30, 2025)
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
- (1) March 1, 2024, through September 18, 2025
EP01: Drill/Exercise Performance (DEP) Sample (IP Section 02.12) (1 Sample)
- (1) April 1, 2024, through June 30, 2025 EP02: Emergency Response Organization (ERO) Drill Participation (IP Section 02.13) (1 Sample)
- (1) April 1, 2024, through June 30, 2025 EP04: Emergency Response Facility and Equipment Readiness (ERFER) (IP Section 02.14) (1 Sample)
- (1) January 1 through June 30, 2025 71152A - Annual Follow-up Problem Identification and Resolution
Annual Follow-up of Selected Issues (Section 03.03) (2 Samples)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) CR1284630, 'C' boric acid storage tank sluiced to unit 2 reactor coolant system following testing activity, on July 1, 2025
- (2) CR1283330, internet service provider service disruption impacts primary communication with Everbridge (DEENS), on September 29, 2025
71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02) (1 Sample)
- (1) The inspectors reviewed the licensees corrective action program to identify potential trends in emergency core cooling system leakage events challenging the capability of the pump room exhaust air cleanup system that might be indicative of a more significant safety issue.
OTHER ACTIVITIES
- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL 60855 - Operation Of An ISFSI Inspections were conducted using the appropriate portions of the IPs in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2690, Inspection Program for Storage of Spent Reactor Fuel and Reactor-Related Greater-than-Class C Waste at Independent Spent Fuel Storage Installations (ISFSI) and for 10 CFR Part 71 Transportation Packagings."
Operation Of An ISFSI (1 Sample)
- (1) From September 16 - 20, 2024, the inspectors performed an onsite review of the licensees ISFSI activities to verify compliance with regulatory requirements. During the on-site inspection, the inspectors observed and reviewed licensee activities in each of the five safety focus areas including occupational exposure, public exposure, fuel damage, confinement, and impact to plant operations.
The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards. The inspectors also performed independent walkdowns of the heavy load lifting equipment and the ISFSI haul path. The inspector also performed an independent radiation survey of the ISFSI pad and evaluated corrective actions associated with loading activities.
INSPECTION RESULTS
Assessment 60855 Assessment of Transfer Cask Loading Misalignment
During a fuel loading campaign in October 2023, the licensee encountered an interference event when a misaligned transfer cask loading rail affected a dry storage canister. Inspectors reviewed the event as part of their sample assessment. The team required technical assistance associated with identification and reporting of defects and noncompliances to complete the evaluation. In the third calendar quarter of 2025, the technical experts affirmed the inspectors' conclusion that the event did not involve any violations of Severity Level IV or of very low safety significance or greater.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On November 19, 2025, the inspectors presented the integrated inspection results to James Jenkins, site vice president, and other members of the licensee staff.
- On September 18, 2025, the inspectors presented the RP occupational radiation safety and transportation baseline inspection results to James Jenkins, site vice president, and other members of the licensee staff.
- On September 18, 2025, the inspectors presented the emergency preparedness program inspection results to J.ames Jenkins and other members of the licensee staff.
- On September 25, 2025, the inspectors presented the baseline ISI inspection results to Matthew Torres, plant manager, and other members of the licensee staff.
- On September 30, 2025, the inspectors presented the operation on an ISFSI inspection results to Robert Page, Licensing Engineer, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
1-OP-14A
Valve Checkoff-Residual Heat Removal
1-OP-6.2A
Valve Checkoff - 1J Engine Cooling Water
1-OP-6.4A
Valve Checkoff - 1J Lube Oil System
Procedures
1-OP-6.5A
Valve Checkoff - Post operational check
Miscellaneous
ETE-CEP-2025-
1003
North Anna Unit 1 - Fall 2025 Steam Generator Integrity
Degradation Assessment (1R31)
08/27/2025
Report #UT-25-
009
UT calibration/examination for component ID# 4-RC-15/ SW-
09/18/2025
Report# PT-25-
003
Liquid penetrant examination for component ID# 14-RC-10/
09/15/2025
Report# PT-25-
004
Liquid penetrant exam on component ID# 4-RC-15/WE-17
09/18/2025
Report# UT-25-
011
UT calibration/examination for component ID# 6-SI-132/ SW-
09/19/2025
NDE Reports
Report# VT-25-
001
Visual examination of pressure retaining bolting (VT-1)
03/30/2025
CR1265806
CR1268295
CR1276529
CR1278366
CR1293459
Corrective Action
Documents
CR1295837
Procedures
OP-NA-601
Protected Equipment
Engineering
Changes
EE-0511
North Anna Station Blackout 125VDC Battery System
Design
07/26/2017
AAC charger-Maintenance Rule Evaluation
Air Operated Valves Purchase Orders NA-125/1125
09/01/1972
NAP-0048
Alternate (AAC) Diesel Generator Sets
2/17/1992
Miscellaneous
VTM E141-00002
2-PT-77.11C
Control Room Chiller 2-HV-E-4C Pump and Valve Test
06/20/2025
Procedures
CA13275385
Perform MRule Functional Failure Evaluation for 00-AAC-
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
BC-1 Unable to Supply 40 Amps at 125VDC
Engineering
Changes
NA-25-00025
Alternate AC Diesel Temporary Battery Charger
Miscellaneous
JF5010
Hindle Power Float Battery Chargers
Corrective Action
Documents
1301592,
1300649
Drawings
11715-FM-088A
Diagram Fuel Pit Cleaning & Refueling Purification System
North Anna Power Station Unit 1
Engineering
Evaluations
ETE-NA-2025-
0034
North Anna Unit 1 Refueling 31 Reactor Vessel Debris
Evaluation
0-AP-27
Malfunction of Spent Fuel Pit System
Procedures
1-OP-5.4
Draining the Reactor Coolant System
ASME Section XI Repair/Replacement Plan
Procedures
1-PT-15.2
Boric Acid Transfer Pump (1-CH-P-2B) Test
Miscellaneous
NA-PROCNA-
ADM-EP-AA-102
(ALERT &
NOTIFICATION
SYSTEM EVAL
23-01-18
North Anna Power Station Alert and Notification System
Evaluation Report
CR1243211
NNOV23FS MCR NRC Communicator Activated ERO
without direction
11/07/2023
CR1243257
NNOV23FS Unanticipated Classification
11/07/2023
CR1254166
Review Surry NCAQ CR1203992 for NAPS E-Plan
Applicability
03/20/2024
CR1264348
UNSAT G.1 Objective (Press Releases) NJUL24BE
07/16/2024
CR1264381
NJULBE24 Obj E.2 UNSAT TSC Offsite Notification DEP
Failure
07/16/2024
CR1264385
EP Exercise Objective I1.2 Overall UNSAT
07/16/2024
CR1264500
NJUL24BE Unsuccessful DEP Opportunity PAR
07/17/2024
CR1269911
Operations below staffing requirements per OP-AA-100
09/25/2024
Corrective Action
Documents
CR1270057
Surry NRC EP Inspection Items: EAL HU4.1 and 10 CFR
50.54Q (AA-22-03) Concerns
09/26/2024
Corrective Action
CR1257432
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Documents
CR1300401
Procedures
C-HP-1071.010, CONTROL OF RADIOACTIVE SOURCES
Radiation Work
Permits (RWPs)
RWP-25-3247
"B" RCP Replacement Project
Corrective Action
Documents
CR# 1239339,
251235,
249331,
250512,
283348,
292876, and
297272.
Various
71151
Procedures
Emergency Preparedness Performance Indicators
Corrective Action
Documents
CR1167451,
1179617,
1181997,
207625,
250893